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Quantitative plasma-fuel and impurity profiling in thick plasma-deposited layers by means of micro ion beam analysis and SIMS
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik.
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik.
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik.
Vise andre og tillknytning
2014 (engelsk)Inngår i: Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, ISSN 0168-583X, E-ISSN 1872-9584, Vol. 332, s. 280-285Artikkel i tidsskrift (Fagfellevurdert) Published
Abstract [en]

The operation of the Joint European Torus (JET) with full-carbon wall during the last decades has proven the importance of material re-deposition processes in remote areas of the tokamak. The thickness of the deposits in shadowed areas can reach 1 mm. The main constituent is carbon, with little inclusion of Inconel components. Atomic fractions Be/C and D/C can locally reach 1. Three methods were used to study thick deposits on JET divertor surfaces: (i) NRA analysis with a 15 mu m wide, 3 MeV He-3 ion microbeam on a polished cross section of the layer to determine the concentration distribution of D, Be and C and the distribution of Ni by particle induced X-ray emission; (ii) elastic proton scattering (EPS) from the top of the layers with a broad proton beam at 3.5 and 4.6 MeV. These methods were absolutely calibrated using thick elemental targets. (iii) Depth profiling of D, Be and Ni was done with secondary ion mass spectrometry (SIMS), sputtering the layers from the surface. The three methods are complementary. The thickest layers are accessible only by microbeam mapping of the cross sections, albeit with limited spatial resolution. The SIMS has the best depth resolution, but is difficult for absolute quantification and is limited in accessible depth. The probed depth with proton backscattering is limited to about 30 mu m. The combination of all three methods provided a coherent picture of the layer composition. It was possible to correlate the SIMS profiling results to quantitative data obtained by the microbeam method.

sted, utgiver, år, opplag, sider
2014. Vol. 332, s. 280-285
Emneord [en]
Scattering Cross-Section, Elastic-Scattering, Divertor, Jet, Erosion, Carbon, Protons, Oxygen, Tiles, Wall
HSV kategori
Identifikatorer
URN: urn:nbn:se:kth:diva-145075DOI: 10.1016/j.nimb.2014.02.078ISI: 000339131200062Scopus ID: 2-s2.0-84902549340OAI: oai:DiVA.org:kth-145075DiVA, id: diva2:716159
Merknad

QC 20140819

Tilgjengelig fra: 2014-05-08 Laget: 2014-05-08 Sist oppdatert: 2017-12-05bibliografisk kontrollert
Inngår i avhandling
1. Experimental studies of materials migration in magnetic confinement fusion devices: Novel methods for measurement of macro particle migration, transport of atomic impurities and characterization of exposed surfaces
Åpne denne publikasjonen i ny fane eller vindu >>Experimental studies of materials migration in magnetic confinement fusion devices: Novel methods for measurement of macro particle migration, transport of atomic impurities and characterization of exposed surfaces
2014 (engelsk)Doktoravhandling, med artikler (Annet vitenskapelig)
Abstract [en]

During several decades of research and development in the field of Magnetically Confined Fusion (MCF) the preferred selection of materials for Plasma Facing Components (PFC) has changed repeatedly. Without doubt, endurance of the first wall will decide research availability and lifespan of the first International Thermonuclear Research Reactor (ITER). Materials erosion, redeposition and mixing in the reactor are the critical processes responsible for modification of materials properties under plasma impact. This thesis presents several diagnostic techniques and their applications for studies of materials transport in fusion devices. The measurements were made at the EXTRAP T2R Reversed Field Pinch operated in Alfvén laboratory at KTH (Sweden), the TEXTOR tokamak, recently shut down at Forschungszentrum Jülich (Germany) and in the JET tokamak at CCFE (UK). The main outcomes of the work are:

  • Development and application of a method for non-destructive capture and characterization of fast dust particles moving in the edge plasma of fusion devices, as well as particles generated upon laser-assisted cleaning of plasma exposed surfaces. 
  • Advancement of conventional broad beam and micro ion beam techniques to include measurement of tritium in the surfaces exposed in future D-T experiments. 
  • Adaption of the micro ion beam method for precision mapping of non uniform elements concentrations on irregular surfaces. 
  • Implementation of an isotopic marker to study the large scale materials migration in a tokamak and development of a method for fast non destructive sampling of the marker on surfaces of PFCs.
sted, utgiver, år, opplag, sider
Stockholm: KTH Royal Institute of Technology, 2014. s. iv, 84
Serie
TRITA-EE, ISSN 1653-5146 ; 2014:024
Emneord
fusion, tokamak, RFP, divertor, limiter, SOL, transport, migration, surface analysis, IBA, ion micro beam, beryllium, tritium
HSV kategori
Forskningsprogram
Fysik
Identifikatorer
urn:nbn:se:kth:diva-145045 (URN)978-91-7595-147-8 (ISBN)
Disputas
2014-05-16, F3, Lindstedsvägen 26, KTH, Stockholm, 14:00 (engelsk)
Opponent
Veileder
Merknad

QC 20140508

Tilgjengelig fra: 2014-05-08 Laget: 2014-05-07 Sist oppdatert: 2014-05-08bibliografisk kontrollert

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